K
Kouichi Maruyama
Researcher at Tohoku University
Publications - 218
Citations - 6298
Kouichi Maruyama is an academic researcher from Tohoku University. The author has contributed to research in topics: Creep & Grain boundary. The author has an hindex of 31, co-authored 216 publications receiving 5623 citations. Previous affiliations of Kouichi Maruyama include Northwestern University.
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Saturation of yield stress and embrittlement in fine lamellar TiAl alloy
TL;DR: In this article, a fully lamellar Ti-39 mol% Al alloy was tested at room temperature and at 950 K. The lamellars varied from 20 to 590 nm, while keeping the same grain size of 90 μm.
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High-temperature mechanical properties of hot-pressed TiN with fine grain size
TL;DR: In this article, fine-grained TiN was studied by compression tests at temperatures ranging from 1073 −1823 K and strain rates from 2×10 −5 to 5×10-3 s −1.
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Different origins of grain size and composition effects on creep in TiAl
TL;DR: Grain size and aluminum content strongly affect the creep rate of single phase 1γ-TiAl as discussed by the authors, and the origin of the grain size and composition dependence have been discussed based on creep curve analysis by the theta concept.
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Microstructural design for thermal creep and radiation damage resistance of titanium aluminide alloys for high-temperature nuclear structural applications
Hanliang Zhu,Tao Wei,D.G. Carr,Robert P. Harrison,Lyndon Edwards,Dongyi Seo,Kouichi Maruyama,Matthew S. Dargusch +7 more
TL;DR: In this paper, the mechanisms for microstructural strengthening and the effects of various micro-structural features on thermal creep and radiation damage resistance of titanium aluminide (TiAl) alloys are reviewed and compared.
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Assessment of Titanium Aluminide Alloys for High-Temperature Nuclear Structural Applications
Hanliang Zhu,Tao Wei,D.G. Carr,Robert P. Harrison,Lyndon Edwards,Wolfgang Hoffelner,Dongyi Seo,Kouichi Maruyama +7 more
TL;DR: In this paper, the microstructure, creep, radiation, and oxidation properties of TiAl alloys in comparison with other nuclear structural materials are compared to assess the potential of these materials as candidate structural materials for future nuclear applications.